ML19331D086

Responds to IE Bulletin 80-13, Cracking in Core Spray Spargers. Util 800331,0627,0702 & 07 Ltrs Encl.Submits Insp Results & Corrective Measures Taken During 1980 Refueling Outage for Spargers & in-vessel Piping

ML19331D086
Person / Time
Site:	Oyster Creek
Issue date:	07/21/1980
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-80-13, NUDOCS 8008270236
Download: ML19331D086 (97)

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Jersey Central Power & Light Company Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 (201)455-8200 Director, Region I U.S. Nuclear Regulatory Comnission July 21, 1980 631 Park Avenue King of Prussia, /A 19406 Cear Sir:

Subject:

Oyster Creek Nuclear Generating Station Ibcket No. 50-219 IE Bulletin No. 80-13 In accordance with IE Bulletin No. 80-13, " Cracking in Core Spray Spargers", this letter submits the results of inspections performed and corrective measures taken for the Oyster Creek Core Spray System spargers and in-vessel piping during the 1980 refueling outage.

The canplete docunentation of these inspections and corrective actions is provided by the following letters to the Director of Nuclear Reactor Regulation:

1.

Letter from I.R. Finfrock, Jr. to Director of NRR dated 3/31/80, subject: " Technical Specification Change Request No. 83",

2.

Letter fran I. R. Finfrock, Jr. to Director of NRR dated 6/27/80, subject: "IE Eulletin l

No. 80-13",

l 3.

Letter from I. R. Finfrock, Jr. to Director of l

NRR dated 7/2/80, subject: " Core Spray System",

1 4.

Letter from I. R. Finfrock, Jr. to Director of NRR dated 7/7/80, subject: " Core Spray System".

A copy of each of these letters is enclosed as an attachment to this letter. This canpletes the reporting requirenents of item 4 under " Actions to be taken by Licensecs" of IE Bulletin No. 80-13 Very truly yours,

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Usn, a IvanR.Fi/cc VicePresiuent[,Jr.

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NRC Office of Inspection and Enforcement Division of Reac ter Cperations Inspection Washington, D. C.

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Jersey Centra! Power & Lcht Co L y sbMber cdne General Puchc Uteties S, stem

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gg rB FM Macisen Avenue at Puncti Scwn Road Momstown. New Jersey 07960 (201)455-8200 July 7, 1980 Director of Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, D. C.

20555

Subject:

Cyster Creek Nuclear Generating Station Docket No. 50-219 Core Spray System Cur letter dated June 27, 1980 provided as an attachment an evaluation of possible cracks on segments of the core spray piping within the reactor vessel between the inlet no::le and the vessel shroud. As a result of our continued evaluation of this problem, our original submittal must be LWted.

General Electric performed an evaluation of cyclic stresses induced by low level dynamic inputs. The conclusion drawn from the evaluation is that the possible crack si:e could increase on the order of 1 to 10 mils per day but it is not expected to grow beyond 8" total length during the next fuel cycle. The attached r placement pages address this mechanism.

Would you please replace the appropriate pages of our enclosure of June 27, 1980.

If you should have any further questions, please contact J. Knubel (201-455-8753) of my staff.

Very truly yours, N.A Ivan R. Fin ock r.

Vice President la l

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Mornstown, New Jersey 07960 (201)455-8200 March 31, 1980 Director of Nuclear Reactor Regulation Nuclear Regulatory Comission Washington, D.C. 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Technical Specification Change Request No. 83 In accordance with 10 CFR 50.59 and 10 CFR S0.90, Jersey Central Power 4 Light Company, owner and operator of the Oyster Creek Nuclear Generating Station, Provisional Operating License No. DPR-16, requests your review and approval of changes to Appendix A of that license.

The Technical Specification change will modify section 4.3 to provide for an augmented inservice inspection of the core spray system

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spargers.

This Technical Specification Change Request has been reviewed and approved by the required review groups in accordance with section 6.4 of the Oyster Creek Technical Specifications.

In addition we have attached supporting information that will A

facilitate your staff's review of this submittal.

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l The proposed repair returns the core spray system to a fully operational state capable of delivering the required core spray. The associated Technical Specification change is requested to augment the inspection requirements to assure continued system functional capability.

As required in 10 CFR Section 170.22, it has been determined that the request is a Class III change and a check for $4000 is enclosed pursuant to that section.

V ry truly ours t

A gJr.

Ivan R. Fi o

Vice Pres dent la 1

Enclosures

1. 4 m 2<p3 7 Jersey Central Power & Lght Comcany is a MemDer of the General Pucic Urates System

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July 2, 1980 Director of Nuclear Reactor Regulation Nuclear Regulatory Co :=ission Washington, D. C.

20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Core Spray System Our letter dated June 27, 1980 to you submitted an evaluation of two (2) possible cracks discovered in the Core Spray piping within the reactor vessel between the inlet no::le and the vessel shroud. On June 30, 1980 there was a meeting between members of my staff and your staff to discuss Jersey Central Power & Light Company's evaluation.

The purpose of this letter is to document our response to questions raised at the June 30 reeting and to supplement our June 27 evaluation.

The attachments to this letter provide the response to the questions raised at the June 30, 1980 meeting.

In addition to the information provided in the attachments, the effect of cracks in the core spray piping located withis reactor vessel between the inlet no::le and the vessel shroud on the triple low (lo-lo-lo) water level indication has been assessed and shows that the effects, if any, will be in the conserva'.ive direction.

A quantitative evaluation on Triple Low water level indication has been initiated and will be forwarded to you when it has been con:pleted.

This report is expected to be co=pleted by August 1, 1980. Also, the technical report supporting Attachment I will be forwarded at that time.

During the next operating cycle, Jersey Central Power 6 i.ight Co pany will continue to work on a develop =ent of better inspection techniques for this location in the vessel. We have been active in the advancement of the

" state of the art" of in-vessel inspection techniques and will continue to pursue i= prove =ents in this area in order to pmvide :: ore definitive information on these types of indicatiens in the future if that is at all possible. We are currently developing tooling and procedures as well as alternate designs to permit replace =ent of the core spray spargers during k

reevl$ (3 Je".ey Cersai Pe*er & Lgn: Cemeany rs a r.' emeer cf tre Gere-al Putec U:24 es Sg em

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